Abstract This paper presents the MELCOR code simulation study regarding how a dedicated severe accident mitigation (SAM) measure the release of radiological FPs to the environment in the spent fuel pool (SFP) of a reference pressurized water reactor (PWR) plant. To draw up relevant insights, a series of accident scenarios have been investigated, taking into account a combination of two initiating events (loss-of-cooling and loss-of-coolant accidents), two SFP operating modes (normal and refueling), and three external water makeup strategies through an external cooling water injection as one of dedicated SAM strategies for a long-term cooling of the SFP. For the analysis, relevant code modeling has been made for a broad spectrum of severe accident-related phenomena being expected during the SFP accidents. As a result, the evolution of relevant physical phenomena has been investigated and discussed in light of the release of FPs, and several points of uncertain issues, which need to address more carefully (a) either when implementing a cross-comparison for different code predictions (such as MELCOR and MAAP) for SFP accident progression or (b) when assessing radiological risk and/or developing dedicated SAM strategies for the SFP of PWR plant, have been drawn up.

中文翻译：

---

压水堆乏燃料池冷却损失和冷却剂事故的放射源术语评估

摘要 本文介绍了 MELCOR 规范模拟研究，涉及专门的严重事故缓解 (SAM) 如何测量参考压水反应堆 (PWR) 工厂乏燃料池 (SFP) 中放射性 FP 向环境的释放。为得出相关见解，研究了一系列事故情景，考虑了两个始发事件（失冷和失冷事故）、两种 SFP 操作模式（正常和加油）以及通过外部冷却水注入的三种外部补水策略作为 SFP 长期冷却的专用 SAM 策略之一。为了进行分析，已针对 SFP 事故期间预期的广泛的严重事故相关现象进行了相关的代码建模。因此，